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Category:Legal-Exhibit
MONTHYEARML15337A3522015-11-17017 November 2015 Official Exhibit - NYS000582-00-BD01 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey ML15337A3372015-11-11011 November 2015 Official Exhibit - ENTR00726-00-BD01 - Track 2 Hearing Exhibit List ML15337A3322015-11-0505 November 2015 Official Exhibit - ENT000726-00-BD01 - Entergy Track 2 Hearing Exhibit List ML15337A3352015-11-0505 November 2015 Official Exhibit - RIVR14001-00-BD01 - Riverkeeper Tailored Track 2 Exhibit List ML15337A3362015-11-0505 November 2015 Official Exhibit - NRCR10001-00-BD01 - NRC Staff Track 2 Exhibit List ML15337A3332015-11-0404 November 2015 Official Exhibit - NYSR25001-00-BD01 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions ML15337A3312015-11-0303 November 2015 Official Exhibit - NRC000230-00-BD01 - Corrections to Prefiled Testimony NRC000168 and NRC000197 ML15337A3262015-10-29029 October 2015 Official Exhibit - ENT000722-00-BD01 - Supplemental Testimony of Entergy Witnesses Nelson Azevedo, Timothy Griesbach & Randy Lott ML15337A3292015-10-29029 October 2015 Official Exhibit - ENTR16001-00-BD01 - Entergy Revised Exhibit List ML15337A3242015-09-23023 September 2015 Official Exhibit - NYS000576-00-BD01 - Pre-Filed Supplemental Testimony of Richard T. Lahey Re Contentions NYS-25, NYS-26B/RK-TC-1B & NYS-38/RK-TC-5 ML15337A3072015-09-0909 September 2015 Official Exhibit - NYS000573-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2962015-09-0909 September 2015 Official Exhibit - NYS000570-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2832015-09-0909 September 2015 Official Exhibit - NYS000563-00-BD01 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28 ML15337A2952015-09-0909 September 2015 Official Exhibit - NYS000569-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2942015-09-0909 September 2015 Official Exhibit - NYS000568-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A2932015-09-0909 September 2015 Official Exhibit - NYS000567-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A3042015-09-0909 September 2015 Official Exhibit - NYS000571-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of David J. Duquette in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2972015-09-0909 September 2015 Official Exhibit - RIV000164-00-BD01 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001) ML15337A3062015-09-0909 September 2015 Official Exhibit - NYS000572-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2822015-09-0909 September 2015 Official Exhibit - NYS000566-00-BD01 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey ML15337A3142015-09-0404 September 2015 Official Exhibit - ENTR00615-PUB-00-BD01 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted ML15334A2842015-08-10010 August 2015 Official Exhibit - ENT000687-00-BD01 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated) ML15335A2932015-08-10010 August 2015 Official Exhibit - NRCR00104-00-BD01 - on Yee Statement of Professional Qualifications (Revised) ML15337A2642015-08-10010 August 2015 Official Exhibit - NRC000196-PUB-00-BD01 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15337A3192015-08-10010 August 2015 Official Exhibit - ENT000698-PUB-00-BD01 - Entergy'S Revised Statement of Position Regarding Contention NYS-38/RK-TC-5(Safety Commitments) (Aug. 10, 2015)Redacted ML15337A3202015-08-10010 August 2015 Official Exhibit - ENT000699-PUB-00-BD01 - Redacted Revised Testimony of Entergy Witnesses Nelson Azevedo, Robert Dolansky, Alan Cox, Jack Strosnider, Timothy Griesbach, Barry Gordon, Randy Lott, and Mark Gray Regarding Contention NYS-38/RK ML15337A3172015-08-10010 August 2015 Official Exhibit - ENT000678-PUB-00-BD01 - NL-07-140, Letter from F. Dacimo, Entergy, to NRC Document Control Desk, ?Reply to Request for Additional Information Regarding License Renewal Application? (Nov. 28, 2007)Redacted ML15337A2652015-08-10010 August 2015 Official Exhibit - NRC000197-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 ML15337A2412015-08-10010 August 2015 Official Exhibit - NRCR00147-00-BD01 - NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised) ML15335A2902015-08-10010 August 2015 Official Exhibit - NRC000222-00-BD01 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15334A2632015-08-10010 August 2015 Official Exhibit - ENT000648-00-BD01 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227 Pressurized Water Reactor Internals Inspection and Evaluat ML15337A2622015-08-10010 August 2015 Official Exhibit - NRC000228-00-BD01 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15337A2452015-08-10010 August 2015 Official Exhibit - NRC000227-00-BD01 - Gary Stevens Statement of Professional Qualifications ML15337A2632015-08-10010 August 2015 Official Exhibit - NRC000229-00-BD01 - Indian Point, Unit 3 Technical Specifications 3.1.4 ML15335A2192015-08-10010 August 2015 Official Exhibit - ENTR00031-00-BD01 - Curriculum Vitae of Alan B. Cox ML15335A2112015-08-10010 August 2015 Official Exhibit - ENTR20186-00-BD01 - Curriculum Vitae of Mark A. Gray ML15337A3162015-08-10010 August 2015 Official Exhibit - ENT000616-PUB-00-BD01 - Testimony of Entergy Witnesses Nelson F. Azevedo, Robert J. Dolansky, Alan B. Cox, Jack R. Strosnider, Timothy J. Griesbach, Randy G. Lott, and Mark A. Gray Regarding Contention NYS-25 (Embrittleme ML15337A2782015-08-10010 August 2015 Official Exhibit - NRC000168-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Dr. Ching Ng, Mr. Gary Stevens, P.E., and Mr. on Yee, Concerning Contentions NYS-26B/RK-TC-1B and NYS-38/RK-TC-5 ML15337A2712015-08-10010 August 2015 Official Exhibit - NRC000223-00-BD01 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15337A2592015-08-10010 August 2015 Official Exhibit - NRC000224-00-BD01 - IP3 FSAR Rev. 04 Chapter 16 ML15337A2442015-08-10010 August 2015 Official Exhibit - NRCR00161-00-BD01 - NRC Staff Testimony of Dr. Allen L. Hiser and Mr. Kenneth J. Karwoski Concerning Portions of State of New York and Riverkeeper, Inc. Joint Contention NYS-38/RK-TC5 (Revised) ML15334A2822015-08-10010 August 2015 Official Exhibit - ENT000680-00-BD01 - Curriculum Vitae of Barry M. Gordon ML15335A2912015-08-10010 August 2015 Official Exhibit - NRCR00118-00-BD01 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised) ML15334A2282015-08-10010 August 2015 Official Exhibit - ENT000634-00-BD01 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts) ML15335A2822015-08-10010 August 2015 Official Exhibit - NRC000220-00-BD01 - Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update, (June 2014) ML15337A2692015-08-10010 August 2015 Official Exhibit - NRC000169-00-BD01 - NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15337A2602015-08-10010 August 2015 Official Exhibit - NRC000226-00-BD01 - Jeffrey C. Poehler Statement of Professional Qualifications ML15335A2732015-08-10010 August 2015 Official Exhibit - NRC000183-00-BD01 - NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) ML15335A2202015-08-10010 August 2015 Official Exhibit - ENTR00184-00-BD01 - Curriculum Vitae of Jack R. Strosnider ML15335A3012015-08-10010 August 2015 Official Exhibit - NRC000206-00-BD01 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) 2015-09-09
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NYS000335 United States Nuclear Regulatory Commission Official Hearing Exhibit Submitted: December 22, 2011 Entergy Nuclear Operations, Inc. EXCERPT In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3) v\..~~p. REGU(.q)<o ASLBP #: 07-858-03-LR-BD01 l~'~
Docket #: 05000247 l 05000286
" 03:
Exhibit #: NYS000335-00-BD01 Identified: 10/15/2012 I-
'" . ~ Admitted: 10/15/2012 Withdrawn:
~
~~
f Rejected: Stricken:
~
NEI 03-08 [Addenda]
Materials Initiative Guidance Addenda to NEI 03*08 Guideline for the Management of Materials Issues June 2009 IPEC00221326 IPEC00221326
NEI03-08 Addendum D (Rev 3)
April 2007 The initial MDM and IMT will be revised/updated as necessary. Following each update, the responsible IP will provide updates to the Strategic Plan as appropriate to ensure that it continues to properly reflect the evolving state of knowledge and experience within the industry.
The current strategic issues identified by the process described above are:
- Nickel Based Alloy see Stress corrosion cracking of Alloy 600 and nickel-based weld material is the single biggest challenge facing the PWR industry. Stress corrosion cracking in RPV-head nozzles, instrument penetrations, pressurizer heater sleeves and piping system butt-welds are frequent occurrences. While symptoms can be detected and in some cases treated, a more fundamental and thorough knowledge is needed to properly explain this phenomenon. Research into the cracking mechanism, mitigation and the key elements affecting crack propagation as well as evaluation of replacement materials and fabrication processes is important for longer term asset management.
- NDE Technology As plants age, new degradation occurs. Recent plant experience with cracking of Alloy 600/821182 materials is an example. Means to accurately detect and size such cracking is paramount to determining component integrity and remaining life. The need for NDE accuracy and sensitivity is a function of in-field geometry and parameters such as component size, materials involved and component function. The technical challenges related to volumetric examination are highly dependent on the metallurgical properties of the material(s) and the configuration, which impacts access to the area of concern. Flaw sizing limitations combined with uncertainty of crack behavior and growth often leads to conservative assumptions and actions to assure component/plant integrity.
A significant component in the effective management of nickel-based alloy weld metal see is the need for appropriate NDE technology to inspect the specific areas of interest and concern. Mitigation strategies rely on being able to ascertain the material conditions prior to applying the mitigation technique. Demonstrated and tested NDE of these nickel based alloy weld materials is needed to support remaining life assessments and to identify flaws prior to occurrence of leakage.
Work on UT technology and development of delivery systems playa key role in our ability to find and manage degradation as well as comply with IOeFR50.
- High Fluence Issues in BWRs and PWRs Reactor internals are subjected to continual neutron fluence. It is known that high fluence leads to reductions in fracture toughness (embrittlement), early initiation of see, and increases in see crack growth rates. However, the degree and rate of these effects is not very well understood. While mitigation strategies are available for locations at low fluences their efficacy at higher fluence levels is not fully understood. Aging D-5 IPEC00221348 IPEC00221348
NEI03-08 Addendum D (Rev 3)
April 2007 management strategies for irradiated stainless steel and nickel based alloys and their weldments depends on early resolution of these issues. Research into this damage mechanism and the key elements affecting the relevant materials of construction, inspection techniques to identify these irradiation assisted degradation mechanisms, as well as evaluation of replacement materials and fabrication processes, is important for longer term asset management.
- Steam Generator Tubing Domestically, steam generator tubes are made from nickel based Alloy 600 as well as higher chromium Alloy 690. The degradation mechanisms affecting steam generator tubing can be several, originating from both primary and secondary sides. Secondary side mechanisms can be complicated and not easily understood. Consequently, to assure prolonged performance of replacement steam generators with Alloy 600TT (thermally treated) and Alloy 690TT tubing, a diligent effort should be made to develop an understanding of the mechanisms involved in the degradation of the original equipment and its possible relevance to new replacement materials.
Laboratory corrosion test data and worldwide in-plant performance data to date of Alloy 600TT and Alloy 690TT indicates superior corrosion-resistant behavior to that exhibited by Alloy 600MA. As such, efforts to confirm this behavior and justify longer periods between tube inspections should be pursued.
- Nuclear Fuel Integrity Fuel cladding is the first of three physical barriers to prevent radioactivity release to the environment. During the last few years, the overall industry fuel failure rate has trended upward as increased fuel duty and new water chemistry environments have been introduced. Improved fuel reliability is the top priority for the industry. This has been recognized by the development of the "Zero Defect Fuels Initiative" in August 2006. As of this date, nuclear fuels issues will be managed under the fuels initiative, not under the Materials Initiative.
- Water Chemistry Water chemistry is cross cutting and can have a direct impact on materials performance and degradation. It is part of the root cause of many degradation issues as well as a potential vehicle for mitigative solutions. Actions taken to minimize problems in one area have potential side effects that may range from innocuous to severe. Improving water chemistry knowledge, identification of parameters to be used by owners to improve chemistry performance at plants and development of mitigation options are keys to managing aging effectively for the future.
As the issue programs develop and align their strategies and work plans to address the strategic issues discussed above, schedules and milestones will be provided indicating when the industry can expect issue resolution. This information will be reflected in future revisions to the Annual Work Plan.
D-6 IPEC00221349 IPEC00221349